The knowledge of the tritium transport parameters in lead lithium is fundamental for the design of the HCLL (helium cooled lead lithium) blanket. In fact, the inventory of tritium in fusion reactors blankets and the permeation of tritium into the blanket coolant, with the consequent leaks toward the environment, are strongly depending on its solubility and diffusivity in the lead alloy PbLi. Several experiments, devoted to investigate the function linking the tritium solubilised in lead lithium with the corresponding tritium partial pressure at equilibrium, were carried out in the past, but significant uncertainties still remain. A detailed analysis of the past experimental works is carried out in this paper with the aim to investigate the main problems occurred in the facilities used to measure the tritium solubility in PbLi that caused such a big spread in the achieved results. On the basis of this analysis, a new a multipurpose laboratory scale apparatus has been designed. The apparatus is able to measure the tritium solubility and diffusivity in PbLi in the range of temperature 300-550 °C and it will be operated with hydrogen partial pressure in the range 102-104Pa. The facility can work with desorption and absorption technique. Moreover, the apparatus has been designed to allow the testing of H/D concentration sensors in Pb-15.7Li in operative conditions relevant to the HCLL-TBM and the characterisation of hydrogen permeation barrier. © 2012 Elsevier B.V.
All Science Journal Classification (ASJC) codes
- Civil and Structural Engineering
- Materials Science(all)
- Nuclear Energy and Engineering
- Mechanical Engineering
Utili, M., Ciampichetti, A., Aiello, A., Ricapito, I., Agostini, P., Desideri, F., & Liger, K. (2012). Design of a multipurpose laboratory scale apparatus for the investigation of hydrogen isotopes in PbLi and permeation technologies. Fusion Engineering and Design, 87(7-8), 1342 - 1346. https://doi.org/10.1016/j.fusengdes.2012.03.013